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Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code

机译:通过RELAP5 / MOD3.2代码对德黑兰研究堆的冷却剂损失事故进行分析

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In this paper, a loss of coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main loss of coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
机译:本文分析了德黑兰研究堆(TRR)的冷却剂泄漏事故(LOCA)。以下过程包括三个主要部分。首先,开发了核心和主要冷却系统的最重要组件的RELAP5节点,并模拟了稳态条件,并将其与实验数据进行了比较[TRR的SAR,2002年10月。德黑兰研究堆的安全分析报告。伊朗原子能组织核研究中心,德黑兰]以验证节点化。然后,选择两个较大的断点进行设计基准事故分析。最后,模拟并开发了两种主要的冷却剂事故损失,以分析TRR中的LOCA。可以得出结论,TRR对LOCA是安全的。 RELAP5 / MOD3.2代码也可以很好地模拟研究堆在运行条件下的运行,但似乎该代码不能像稳态条件那样精确地模拟研究堆的大过渡相,特别是在低压两相混合物(水和空气)中。

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